ML20059M350
| ML20059M350 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/25/1990 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20059M322 | List: |
| References | |
| NUDOCS 9010040097 | |
| Download: ML20059M350 (2) | |
Text
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4.4.1.5 Reactor Building Modifications Any major modification or replacement of components affecting the reactor building integrity shall be followed by either an integrated l
1eak rate test or a local leak test, as appropriate, and shall r.eet the acceptance criteria of 4.4.1.1.6 and 4.4.1.2.3, respectively.
4.4.1.6 Operability of Access Hatch Interlocks l
1.
At least once per six months the operability of the personnel and emergency hatch door interlocks and the associated control room annunciator circuits shall be determined.
If the interlock permits both doors to be open at the same time or does not provide accurate status indication in the control room the interlock shall be declared inoperable.
i 2.
During periods when containment integrity is required and an interlock it inoperable, each entry and exit via that airlock shall be locally supervised by a member of the unit operating maintenance or technical staffs, to assure that only one door is open at any time and that both doors are properly closed following use.
A record of supervision and verification of closure shall be maintained during periods of interlock inoperability in an appropriate station log.
3.
If an interlock is inoperable for more than 14 days following determination of inoperability, use of the airlock, except for emergency purposes, shall be suspended until the interlock is returned to operable status.
4.4.1.7 Operability of Purge Valves 1.
A periodic pressurization of the purgo valve interspaces to 50.6 psig per Specification 4.4.1.2.5.d shall be performed to help assure timely detection and resolution of valve and/or actuator degradation. The acceptance criteria is that total
'ocal leakage when updated for-the new purge valve leakage thall be less than 0.6L4 See Specification 3.6.8 for forther action.
2.
The rebber seats on purge valves shall be visually examined and durometer tested each refueling interval to detect degradation (e.g. cracking, brittleness, etc.) and to assure timely cleaning, lubrication, and seat replacement.
P 4-34 Amendment Nos. 63, 108, 113, 151 9010040097 900925 POR ADOCK 05000289 P
l More frequent testing of various penetrations is specified as these locations are more susceptible to leakage than the reactor building liner due to the mechanical closure involved. The basis for 1'
specifying a total leakage rate of 0.6 L. from those penetrations and isolation valves is that more than one-half of the allowable integrated leakage rate will be from these sources.
Valve operability tests are specified to assure proper closure or opening of the reactor building isolation valves to provide for isolation or functioning of Engineered Safety Features systems.
Valves will be stroked to the position required to fulfill their safety function un',ess it is establish that such testing is not practical during operation. Valves that cannot be full-stroke tested i
will be part-stroke tested during operation and full-stroke tested during each normal refueling shutdown.
Periodic surveillance of the airlock interlock systems is specified i
to assure continued operability and preclude instances where one or both doors are inadvertently left open. When an airlock is inoperable and containment integrity is required, local supervision of airlock operation is specified.
Purge valve interspace pressurization test operability requirements, inspections, and durometer testing provide a high degree of assurance of purge valve performance as containment isolation barriers.
Reference (1) FSAR, Chapter 5.
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4-34b Amendment Nos. 36, 63, 108, 113, 151 l
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